US20200035370A1 - Environmentally sequestered spent fuel pool - Google Patents

Environmentally sequestered spent fuel pool Download PDF

Info

Publication number
US20200035370A1
US20200035370A1 US16/584,892 US201916584892A US2020035370A1 US 20200035370 A1 US20200035370 A1 US 20200035370A1 US 201916584892 A US201916584892 A US 201916584892A US 2020035370 A1 US2020035370 A1 US 2020035370A1
Authority
US
United States
Prior art keywords
pool
liner
spent fuel
fuel pool
cavity
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Abandoned
Application number
US16/584,892
Inventor
Krishna P. Singh
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Holtec International Inc
Original Assignee
Holtec International Inc
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Holtec International Inc filed Critical Holtec International Inc
Priority to US16/584,892 priority Critical patent/US20200035370A1/en
Assigned to HOLTEC INTERNATIONAL reassignment HOLTEC INTERNATIONAL ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: SINGH, KRISHNA P
Publication of US20200035370A1 publication Critical patent/US20200035370A1/en
Priority to US17/088,960 priority patent/US11515054B2/en
Priority to US17/981,978 priority patent/US20230082771A1/en
Abandoned legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02Details of handling arrangements
    • G21C19/06Magazines for holding fuel elements or control elements
    • G21C19/07Storage racks; Storage pools
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/10Means for preventing contamination in the event of leakage, e.g. double wall
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/002Detection of leaks
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01MTESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
    • G01M3/00Investigating fluid-tightness of structures
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/40

Definitions

  • the present invention generally relates to storage of nuclear fuel assemblies, and more particularly to an improved spent fuel pool for wet storage of such fuel assemblies.
  • a spent fuel pool (sometimes, two or more) is an integral part of every nuclear power plant.
  • standalone wet storage facilities have also been built to provide additional storage capacity for the excess fuel discharged by the reactors.
  • An autonomous wet storage facility that serves one or more reactor units is sometimes referred to by the acronym AFR meaning “Away-from-Reactor.” While most countries have added to their in-plant used fuel storage capacity by building dry storage facilities, the French nuclear program has been the most notable user of AFR storage.
  • the spent fuel pool stores the fuel irradiated in the plant's reactor in a deep pool of water.
  • the pool is typically 40 feet deep with upright Fuel Racks positioned on its bottom slab. Under normal storage conditions, there is at least 25 feet of water cover on top of the fuel to ensure that the dose at the pool deck level is acceptably low for the plant workers.
  • Fuel pools at most (but not all) nuclear plants are at grade level, which is desirable from the standpoint of structural capacity of the reinforced concrete structure that forms the deep pond of water.
  • the liners have generally served reliably at most nuclear plants, but isolated cases of water seepage of pool water have been reported. Because the pool's water bears radioactive contaminants (most of it carried by the crud deposited on the fuel during its “burn” in the reactor), leaching out of the pool water to the plant's substrate, and possibly to the underground water, is evidently inimical to public health and safety. To reduce the probability of pool water reaching the ground water, the local environment and hence some AFR pools have adopted the pool-in-pool design wherein the fuel pool is enclosed by a secondary outer pool filled with clean water. In the dual-pool design, any leakage of water from the contaminated pool will occur into the outer pool, which serves as the barrier against ground water contamination.
  • the dual pool design has several unattractive aspects, viz.: (1) the structural capacity of the storage system is adversely affected by two reinforced concrete containers separated from each other except for springs and dampers that secure their spacing; (2) there is a possibility that the outer pool may leak along with the inner pool, defeating both barriers and allowing for contaminated water to reach the external environment; and (3) the dual-pool design significantly increases the cost of the storage system.
  • the present invention provides an environmentally sequestered spent fuel pool system having a dual impervious liner system and leak detection/evacuation system configured to collect and identify leakage in the interstitial space formed between the liners.
  • the internal cavity of the pool has not one but two liners layered on top of each other, each providing an independent barrier to the out-migration (emigration) of pool water.
  • Each liner encompasses the entire extent of the water occupied space and further extends above the pool's “high water level.”
  • the top of the pool may be equipped with a thick embedment plate (preferably 2 inches thick minimum in one non-limiting embodiment) that circumscribes the perimeter of the pool cavity at its top extremity along the operating deck of the pool.
  • Each liner may be independently welded to the top embedment plate.
  • the top embedment plate features at least one telltale hole, which provides direct communication with the interstitial space between the two liner layers.
  • a vapor extraction system comprising a vacuum pump downstream of a one-way valve is used to draw down the pressure in the inter-liner space through the telltale hole to a relatively high state of vacuum.
  • the absolute pressure in the inter-liner space (“set pressure”) preferably should be such that the pool's bulk water temperature is above the boiling temperature of water at the set pressure as further described herein.
  • an environmentally sequestered nuclear spent fuel pool system includes: a base slab; a plurality of vertical sidewalls extending upwards from and adjoining the base slab, the sidewalls forming a perimeter; a cavity collectively defined by the sidewalls and base slab that holds pool water; a pool liner system comprising an outer liner adjacent the sidewalls, an inner liner adjacent the outer liner and wetted by the pool water, and an interstitial space formed between the liners; a top embedment plate circumscribing the perimeter of the pool at a top surface of the sidewalls adjoining the cavity; and the inner and outer sidewalls having top terminal ends sealably attached to the embedment plate.
  • an environmentally sequestered nuclear spent fuel pool with leakage detection system includes: a base slab; a plurality of vertical sidewalls extending upwards from and adjoining the base slab, the sidewalls forming a perimeter; a cavity collectively defined by the sidewalls and base slab that holds pool water; at least one fuel storage rack disposed in the cavity that holds a nuclear spent fuel assembly containing nuclear fuel rods that heat the pool water; a pool liner system comprising an outer liner adjacent the sidewalls and base slab, an inner liner adjacent the outer liner and wetted by the pool water, and an interstitial space formed between the liners; a top embedment plate circumscribing the perimeter of the pool, the embedment plate embedded in the sidewalls adjoining the cavity; the inner and outer liners attached to the top embedment plate; a flow plenum formed along the sidewalls that is in fluid communication with the interstitial space; and a vacuum pump fluidly coupled to the flow plenum, the vacuum pump operable to evacuate the interstitial space to
  • a method for detecting leakage from a nuclear spent fuel pool includes: providing a spent fuel pool comprising a plurality of sidewalls, a base slab, a cavity containing cooling water, and a liner system disposed in the cavity including an outer liner, an inner liner, and an interstitial space between the liner; placing a fuel storage rack in the pool; inserting at least one nuclear fuel assembly into the storage rack, the fuel assembly including a plurality of spent nuclear fuel rods; heating the cooling water in the pool to a first temperature from decay heat generated by the spent nuclear fuel rods; drawing a vacuum in the interstitial space with a vacuum pump to a negative pressure having a corresponding boiling point temperature less than the first temperature; collecting cooling water leaking from the pool through the liner system in the interstitial space; converting the leaking cooling water into vapor via boiling; and extracting the vapor from the interstitial space using the vacuum pump; wherein the presence of vapor in the interstitial space allows detection of a liner breach.
  • the method may further include discharging the vapor extracted by the vacuum pump through a charcoal filter to remove contaminants.
  • the method may further include: monitoring a pressure in the interstitial space; detecting a first pressure in the interstitial space prior to collecting cooling water leaking from the pool through the liner system in the interstitial space; and detecting a second pressure higher than the first pressure after collecting cooling water leaking from the pool through the liner system in the interstitial space; wherein the second pressure is associated with a cooling water leakage condition.
  • FIG. 1 is a cross sectional diagram of a known approach used to monitor the integrity of weld seams for leakage in a single spent fuel pool liner system;
  • FIG. 2 is a side cross-sectional view of an environmentally sequestered nuclear spent fuel pool having a dual liner and leakage collection and monitoring system according to the present disclosure
  • FIG. 3 is a top plan view of the fuel pool with liner and leakage collection/monitoring system of FIG. 2 ;
  • FIG. 4 is a detail taken from FIG. 2 showing a bottom joint of the liner system at the intersection of liners from the sidewalls and base slab of the fuel pool;
  • FIG. 5 is a detail taken from FIG. 2 showing a top joint of the liner system at the terminal top ends of the sidewall liners;
  • FIG. 6 is a perspective view of an example nuclear fuel assembly containing spent nuclear fuel rods.
  • FIG. 7 is a schematic diagram of a vacuum leakage collection and monitoring system according to the present disclosure.
  • any reference to direction or orientation is merely intended for convenience of description and is not intended in any way to limit the scope of the present invention.
  • Relative terms such as “lower,” “upper,” “horizontal,” “vertical,”, “above,” “below,” “up,” “down,” “top” and “bottom” as well as derivative thereof (e.g., “horizontally,” “downwardly,” “upwardly,” etc.) should be construed to refer to the orientation as then described or as shown in the drawing under discussion. These relative terms are for convenience of description only and do not require that the apparatus be constructed or operated in a particular orientation.
  • an environmentally sequestered spent fuel pool system includes a spent fuel pool 40 comprising a plurality of vertical sidewalls 41 rising upwards from an adjoining substantially horizontal base wall or slab 42 (recognizing that some slope may intentionally be provided in the upper surface of the bottom wall for drainage toward a low point if the pool is to be emptied and rinsed/decontaminated at some time and due to installation tolerances).
  • the base slab 42 and sidewalls 41 may be formed of reinforced concrete in one non-limiting embodiment.
  • the fuel pool base slab 42 may be formed in and rest on the soil sub-grade 26 the top surface of which defines grade G. In this embodiment illustrated in the present application, the sidewalls are elevated above grade. In other possible embodiments contemplated, the base slab 42 and sidewalls 41 may alternatively be buried in sub-grade 26 which surrounds the outer surfaces of the sidewalls. Either arrangement may be used and does not limit of the invention.
  • the spent fuel pool 40 may have a rectilinear shape in top plan view.
  • Four sidewalls 41 may be provided in which the pool has an elongated rectangular shape (in top plan view) with two longer opposing sidewalls and two shorter opposing sidewalls (e.g. end walls).
  • Other configurations of the fuel pool 40 are possible such as square shapes, other polygonal shapes, and non-polygonal shapes.
  • the sidewalls 41 and base slab 42 of the spent fuel pool 40 define a cavity 43 configured to hold cooling pool water W and a plurality of submerged nuclear spent fuel assembly storage racks 27 holding fuel bundles or assemblies 28 each containing multiple individual nuclear spent fuel rods.
  • the storage racks 27 are disposed on the base slab 42 in typical fashion.
  • the spent fuel pool 40 extends from an operating deck 22 surrounding the spent fuel pool 40 downwards to a sufficient depth D 1 to submerge the fuel assemblies 28 (see, e.g. FIG. 6 ) beneath the surface level S of the pool water W for proper radiation shielding purposes.
  • the fuel pool may have a depth such that at least 10 feet of water is present above the top of the fuel assembly.
  • a nuclear fuel assembly storage rack 27 is shown in FIGS. 2 and 3, and further described in commonly assigned U.S. patent application Ser. No. 14/367,705 filed Jun. 20, 1014, which is incorporated herein by reference in its entirety.
  • the storage rack 27 contains a plurality of vertically elongated individual cells as shown each configured for holding a fuel assembly 28 comprising a plurality of individual nuclear fuel rods.
  • An elongated fuel assembly 28 is shown in FIG. 6 holding multiple fuel rods 28 a and further described in commonly assigned U.S. patent application Ser. No. 14/413,807 filed Jul. 9, 2013, which is incorporated herein by reference in its entirety.
  • Typical fuel assemblies 28 for a pressurized water reactor may each hold over 150 fuel rods in 10 ⁇ 10 to 17 ⁇ 17 fuel rod grid arrays per assembly.
  • the assemblies may typically be on the order of approximately 14 feet high weighing about 1400-1500 pounds each.
  • the substantially horizontal operating deck 22 that circumscribes the sidewalls 41 and pool 40 on all sides in one embodiment may be formed of steel and/or reinforced concrete.
  • the surface level of pool water W (i.e. liquid coolant) in the pool 40 may be spaced below the operating deck 22 by a sufficient amount to prevent spillage onto the deck during fuel assembly loading or unloading operations and to account to seismic event.
  • the surface of the operating deck 22 may be at least 5 feet above the maximum 100 year flood level for the site in one embodiment.
  • the spent fuel pool 40 extending below the operating deck level may be approximately 40 feet or more deep (e.g. 42 feet in one embodiment).
  • the fuel pool is long enough to accommodate as many spent fuel assemblies as required. In one embodiment, the fuel pool 40 may be about 60 feet wide.
  • a spent fuel pool liner system comprising a double liner is provided to minimize the risk of pool water leakage to the environment.
  • the liner system is further designed to accommodate cooling water leakage collection and detection/monitoring to indicate a leakage condition caused by a breach in the integrity of the liner system.
  • the liner system comprises a first outer liner 60 separated from a second inner liner 61 by an interstitial space 62 formed between the liners.
  • An outside surface of liner 60 is disposed against or at least proximate to the inner surface 63 of the fuel pool sidewalls 41 and opposing inside surface is disposed proximate to the interstitial space 62 and outside surface of liner 61 .
  • the inside surface of liner 61 is contacted and wetted by the fuel pool water W. It bears noting that placement of liner 60 against liner 61 without spacers therebetween provides a natural interstitial space of sufficient width to allow the space and any pool leakage there-into to be evacuated by a vacuum system, as further described herein.
  • each liner 60 , 61 may be made of any suitable metal which is preferably resistant to corrosion, including without limitation stainless steel, aluminum, or other.
  • each liner may be comprised of multiple substantially flat metal plates which are seal welded together along their peripheral edges to form a continuous liner system encapsulating the sidewalls 41 and base slab 42 of the spent fuel pool 40 .
  • the inner and outer liners 61 , 60 may have the same or different thicknesses (measured horizontally or vertically between major opposing surfaces of the liners depending on the position of the liners). In one embodiment, the thicknesses may be the same. In some instances, however, it may be preferable that the inner liner 61 be thicker than the outer liner 60 for potential impact resistant when initially loading empty fuel storage racks 27 into the spent fuel pool 40 .
  • the outer and inner liners 60 , 61 extend along the vertical sidewalls 41 of the spent fuel pool 40 and completely across the horizontal base slab 42 in one embodiment to completely cover the wetted surface area of the pool.
  • the horizontal sections of liners 60 b, 61 b on the base slab 42 may be joined to the vertical sections 60 a, 61 a along the sidewalls 41 of the pool 40 by welding.
  • the bottom liner joint 64 comprises the use of seal welds 65 (e.g. illustrated fillet welds or other) to seal sections 60 a to 60 b along their respective terminal edges and sections 61 a to 61 b along their respective terminal edges as shown.
  • the joint 64 is configured and arranged to fluidly connect the horizontal interstitial space 64 between horizontal liner sections 60 b, 61 b to the vertical interstitial space 64 between vertical liner sections 60 a, 61 a for reasons explained elsewhere herein.
  • the top liner joint 65 in one non-limiting embodiment between the top terminal edges 60 c, 61 c of the vertical liner sections 60 a, 61 a is shown in the detail of FIG. 5 .
  • the top of the spent fuel pool 40 is equipped with a substantially thick metal embedment plate 70 which circumscribes the entire perimeter of the fuel pool.
  • the embedment plate 70 may be continuous in one embodiment and extends horizontally along the entire inner surface 63 of the sidewalls 41 at the top portion of the sidewalls.
  • the embedment plate 70 has an exposed portion of the inner vertical side facing the pool which extends above the top terminal ends 60 c, 61 c of the inner and outer liners 60 , 61 .
  • the opposing outer vertical side of the plate 70 is embedded entirely into the sidewalls 41 .
  • a top surface 71 of the embedment plate 70 that faces upwards may be substantially flush with the top surface 44 of the sidewalls 41 to form a smooth transition therebetween. In other possible implementations, the top surface 71 may extend above the top surface 44 of the sidewalls.
  • the embedment plate 70 extends horizontal outward from the fuel pool 40 for a distance into and less than the lateral width of the sidewalls 41 as shown.
  • the embedment plate 70 has a horizontal thickness greater than the horizontal thickness of the inner liner 61 , outer liner 60 , and in some embodiments both the inner and outer liners combined.
  • the top embedment plate 70 is embedded into the top surface 44 of the concrete sidewalls 41 has a sufficient vertical depth or height to allow the top terminal edges 60 c, 61 c of liners 60 , 61 (i.e. sections 60 a and 61 a respectively) to be permanently joined to the plate.
  • the top terminal edges of liners 60 , 61 terminate at distances D 2 and D 1 respectively below a top surface 71 of the embedment plate 70 (which in one embodiment may be flush with the top surface of the pool sidewalls 41 as shown).
  • Distance D 1 is less than D 2 such that the outer liner 60 is vertical shorter in height than the inner liner 61 .
  • the embedment plate 70 has a bottom end which terminates below the top terminal edges 60 c, 61 c of the liners 60 , 61 to facilitate for welding the liners to the plate.
  • the embedment plate 70 may be formed of a suitable corrosion resistant metal such as stainless steel, aluminum, or another metal which preferably is compatible for welding to the metal used to construct the outer and inner pool liners 60 , 61 without requiring dissimilar metal welding.
  • a suitable corrosion resistant metal such as stainless steel, aluminum, or another metal which preferably is compatible for welding to the metal used to construct the outer and inner pool liners 60 , 61 without requiring dissimilar metal welding.
  • the top terminal edges 60 c, 61 c of inner and outer liners 60 , 61 may have a vertically staggered arranged and be separately seal welded to the top embedment plate 70 independently of each other.
  • a seal weld 66 couples the top terminal edge 61 c of liner 61 to the exposed portion of the inner vertical side of the embedment plate 70 .
  • a second seal weld 67 couples the top terminal edge 60 c of liner 60 also to the exposed portion of the inner vertical side of the embedment plate 70 at a location below and spaced vertical apart from seal weld 66 . This defines a completely and hermetically sealed enclosed flow plenum 68 that horizontal circumscribes the entire perimeter of the spent fuel pool 40 in one embodiment.
  • the flow plenum 68 is in fluid communication with the interstitial space 62 as shown.
  • One vertical side of the flow plenum is bounded by a portion of inner liner 61 and the opposing vertical side of the plenum is bounded by the inner vertical side of the top embedment plate 70 .
  • the top flow plenum 68 may be continuous or discontinuous in some embodiments. Where discontinuous, it is preferable that a flow passageway 105 in the top embedment plate 70 be provided for each section of the separate passageways.
  • Seal welds 66 and 67 may be any type of suitable weld needed to seal the liners 60 , 61 to the top embedment plate 70 .
  • Backer plates, bars, or other similar welding accessories may be used to make the welds as needed depending on the configuration and dimensions of the welds used. The invention is not limited by the type of weld.
  • the outer and inner liners 60 , 61 are sealably attached to the spent fuel pool 40 only at top embedment plate 70 .
  • the remaining portions of the liners below the embedment plate may be in abutting contact with the sidewalls 41 and base slab 42 without means for fixing the liners to these portions.
  • At least the inner liner 61 has a height which preferably is higher than the anticipated highest water level (surface S) of the pool water W in one embodiment. If the water level happens to exceed that for some reason, the top embedment plate 70 will be wetted directly by the pool water and contain the fluid to prevent overflowing the pool onto the operating deck 22 .
  • a vapor extraction or vacuum system 100 is provided that is used to draw down the air pressure in the interstitial space between the outer and inner liners 60 , 61 to a relatively high state of vacuum for leakage control and/or detection.
  • FIG. 7 is a schematic diagram of one embodiment of a vacuum system 100 .
  • vacuum system 100 generally includes a vacuum pump 101 and a charcoal filter 102 .
  • Vacuum pump 101 may be any suitable commercially-available electric-driven vacuum pump capable of creating a vacuum or negative pressure within the interstitial space 62 between the pool liners 60 and 61 .
  • the vacuum pump 101 is fluidly connected to the interstitial space 68 via a suitable flow conduit 103 which is fluidly coupled to a telltale or flow passageway 105 extending from the top surface 71 of the top embedment plate 70 to the top flow plenum 68 formed between the pool liners 60 and 61 .
  • Flow conduit 103 may be formed of any suitable metallic or non-metallic tubing or piping capable of withstanding a vacuum.
  • a suitably-configured fluid coupling 104 may be provided and sealed to the outlet end of the flow passageway 105 for connecting the flow conduit 103 .
  • the inlet end of the flow passageway penetrates the inner vertical side of top embedment plate 70 within the flow plenum 68 .
  • the flow passageway 105 and external flow conduit 103 provides a contiguous flow conduit that fluidly couples the flow plenum 68 to the vacuum pump 101 .
  • a one-way check valve is disposed between the flow plenum 105 and the suction inlet of the vacuum pump 101 to permit air and/or vapor to flow in a single direction from the liner system to the pump.
  • the absolute pressure maintained by the vacuum system 100 in the interstitial space 62 between the liners 60 , 61 preferably should be such that the bulk water temperature of the spent fuel pool 40 which is heated by waste decay heat generated from the fuel rods/assemblies is above the boiling temperature of water at the set pressure.
  • set pressure The table below provides the boiling temperature of water at the level of vacuum in inches of mercury (Hg) which represent some examples of set pressures that may be used.
  • any significant rise in pressure would indicate potential leakage of water in the interstitial space 62 between the liners 60 , 61 . Because of sub-atmospheric conditions maintained by the vacuum pump 101 in the interstitial space, any water that may leak from the pool into this space through the inner liner 61 would evaporate, causing the pressure to rise which may be monitored and detected by a pressure sensor 104 .
  • the vacuum pump 101 preferably should be set to run and drive down the pressure in the interstitial space 62 to the “set pressure.”
  • the vacuum pump 101 is operated to create a negative pressure (vacuum) in the interstitial space 62 of 2 inches of Hg, the corresponding boiling point of water at that negative pressure is 101 degrees Fahrenheit (degrees F.) from the above Table. If the bulk water temperature of pool water W in the spent fuel pool 40 were at any temperature above 101 degrees F. and leakage occurred through the inner pool liner 61 into the interstitial space 62 , the liquid leakage would immediately evaporate therein creating steam or vapor. The vacuum pump 101 withdraws the vapor through the flow plenum 68 , flow passageway 105 in the top embedment plate 70 , and flow conduit 103 (see, e.g.
  • Pressure sensor 104 disposed on the suction side of the pump 101 would detect a corresponding rise in pressure indicative of a potential leak in the liner system.
  • the pressure sensor 104 may be operably linked to a control panel of a properly configured computer processor based plant monitoring system 107 which monitors and detects the pressure measured in the interstitial space 62 between the liners on a continuous or intermittent basis to alert operators of a potential pool leakage condition.
  • plant monitoring systems are well known in the art without further elaboration.
  • the extracted vapor in the exhaust or discharge from the vacuum pump 101 is routed through a suitable filtration device 102 such as a charcoal filter or other type of filter media before discharge to the atmosphere, thereby preventing release of any particulate contaminants to the environment.
  • a suitable filtration device 102 such as a charcoal filter or other type of filter media
  • the second outer liner 60 encapsulating the fuel pool provides a secondary barrier and line of defense to prevent direct leaking of pool water W into the environment.
  • vapor extraction systems including a telltale passageway, vacuum pump, and filter combination with leakage monitoring/detection capabilities that may be provided.
  • four independent systems may provide adequate redundancy.
  • a third or even fourth layer of liner may be added to increase the number of barriers against leakage of pool water to the environment.
  • a third layer in some instances may be used as a palliative measure if the leak tightness of the first inter-liner space could not, for whatever reason, be demonstrated by a high fidelity examination in the field such as helium spectroscopy.

Abstract

An environmentally sequestered nuclear spent fuel pool in one embodiment includes sidewalls and a base slab that confine a water impoundment. The pool includes fuel racks containing spent fuel assemblies which heat the water via radioactive decay. A dual liner system enclosing the pool forms an impervious barrier providing redundant provisions for preventing leakage of contaminated pool water into the environment. An interstitial space is formed between the liners which may be maintained at sub-atmospheric pressures by a vacuum pump system that evacuates the space. By maintaining the pressure in the space at a negative pressure with corresponding boiling point less than the temperature of the pool water, any leakage through the inner-most liner into the interstitial space will vaporize and be extracted via the pump for signaling a potential leak in the liner system.

Description

    CROSS-REFERENCE TO RELATED APPLICATIONS
  • The present application is a continuation of U.S. patent application Ser. No. 14/877,217, filed Oct. 7, 2015, which claims the benefit of priority to U.S. Provisional Application No. 62/061,089, filed Oct. 7, 2014, the entireties of which are incorporated herein by reference.
  • BACKGROUND
  • The present invention generally relates to storage of nuclear fuel assemblies, and more particularly to an improved spent fuel pool for wet storage of such fuel assemblies.
  • A spent fuel pool (sometimes, two or more) is an integral part of every nuclear power plant. At certain sites, standalone wet storage facilities have also been built to provide additional storage capacity for the excess fuel discharged by the reactors. An autonomous wet storage facility that serves one or more reactor units is sometimes referred to by the acronym AFR meaning “Away-from-Reactor.” While most countries have added to their in-plant used fuel storage capacity by building dry storage facilities, the French nuclear program has been the most notable user of AFR storage.
  • As its name implies, the spent fuel pool (SFP) stores the fuel irradiated in the plant's reactor in a deep pool of water. The pool is typically 40 feet deep with upright Fuel Racks positioned on its bottom slab. Under normal storage conditions, there is at least 25 feet of water cover on top of the fuel to ensure that the dose at the pool deck level is acceptably low for the plant workers. Fuel pools at most (but not all) nuclear plants are at grade level, which is desirable from the standpoint of structural capacity of the reinforced concrete structure that forms the deep pond of water. To ensure that the pool's water does not seep out through the voids and discontinuities in the pool slab or walls, fuel pools in nuclear plants built since the 1970s have always been lined with a thin single-layer stainless steel liner (typically in the range of 3/16 inch to 5/16 inch thick). The liner is made up of sheets of stainless steel (typically ASTM 240-304 or 304L) seam welded along their contiguous edges to form an impervious barrier between the pool's water and the undergirding concrete. In most cases, the welded liner seams are monitored for their integrity by locating a leak chase channel underneath them (see, e.g. FIG. 1). The leak chase channels' detection ability, however, is limited to welded regions only; the base metal area of the liner beyond the seams remains un-surveilled.
  • The liners have generally served reliably at most nuclear plants, but isolated cases of water seepage of pool water have been reported. Because the pool's water bears radioactive contaminants (most of it carried by the crud deposited on the fuel during its “burn” in the reactor), leaching out of the pool water to the plant's substrate, and possibly to the underground water, is evidently inimical to public health and safety. To reduce the probability of pool water reaching the ground water, the local environment and hence some AFR pools have adopted the pool-in-pool design wherein the fuel pool is enclosed by a secondary outer pool filled with clean water. In the dual-pool design, any leakage of water from the contaminated pool will occur into the outer pool, which serves as the barrier against ground water contamination. The dual pool design, however, has several unattractive aspects, viz.: (1) the structural capacity of the storage system is adversely affected by two reinforced concrete containers separated from each other except for springs and dampers that secure their spacing; (2) there is a possibility that the outer pool may leak along with the inner pool, defeating both barriers and allowing for contaminated water to reach the external environment; and (3) the dual-pool design significantly increases the cost of the storage system.
  • Prompted by the deficiencies in the present designs, a novel design of a spent nuclear fuel pool that would guarantee complete confinement of pool's water and monitoring of the entire liner structure including seams and base metal areas is desirable.
  • SUMMARY
  • The present invention provides an environmentally sequestered spent fuel pool system having a dual impervious liner system and leak detection/evacuation system configured to collect and identify leakage in the interstitial space formed between the liners. The internal cavity of the pool has not one but two liners layered on top of each other, each providing an independent barrier to the out-migration (emigration) of pool water. Each liner encompasses the entire extent of the water occupied space and further extends above the pool's “high water level.” The top of the pool may be equipped with a thick embedment plate (preferably 2 inches thick minimum in one non-limiting embodiment) that circumscribes the perimeter of the pool cavity at its top extremity along the operating deck of the pool. Each liner may be independently welded to the top embedment plate. The top embedment plate features at least one telltale hole, which provides direct communication with the interstitial space between the two liner layers. In one implementation, a vapor extraction system comprising a vacuum pump downstream of a one-way valve is used to draw down the pressure in the inter-liner space through the telltale hole to a relatively high state of vacuum. The absolute pressure in the inter-liner space (“set pressure”) preferably should be such that the pool's bulk water temperature is above the boiling temperature of water at the set pressure as further described herein.
  • In one embodiment, an environmentally sequestered nuclear spent fuel pool system includes: a base slab; a plurality of vertical sidewalls extending upwards from and adjoining the base slab, the sidewalls forming a perimeter; a cavity collectively defined by the sidewalls and base slab that holds pool water; a pool liner system comprising an outer liner adjacent the sidewalls, an inner liner adjacent the outer liner and wetted by the pool water, and an interstitial space formed between the liners; a top embedment plate circumscribing the perimeter of the pool at a top surface of the sidewalls adjoining the cavity; and the inner and outer sidewalls having top terminal ends sealably attached to the embedment plate.
  • In another embodiment, an environmentally sequestered nuclear spent fuel pool with leakage detection system includes: a base slab; a plurality of vertical sidewalls extending upwards from and adjoining the base slab, the sidewalls forming a perimeter; a cavity collectively defined by the sidewalls and base slab that holds pool water; at least one fuel storage rack disposed in the cavity that holds a nuclear spent fuel assembly containing nuclear fuel rods that heat the pool water; a pool liner system comprising an outer liner adjacent the sidewalls and base slab, an inner liner adjacent the outer liner and wetted by the pool water, and an interstitial space formed between the liners; a top embedment plate circumscribing the perimeter of the pool, the embedment plate embedded in the sidewalls adjoining the cavity; the inner and outer liners attached to the top embedment plate; a flow plenum formed along the sidewalls that is in fluid communication with the interstitial space; and a vacuum pump fluidly coupled to the flow plenum, the vacuum pump operable to evacuate the interstitial space to a negative set pressure below atmospheric pressure.
  • A method for detecting leakage from a nuclear spent fuel pool is provided. The method includes: providing a spent fuel pool comprising a plurality of sidewalls, a base slab, a cavity containing cooling water, and a liner system disposed in the cavity including an outer liner, an inner liner, and an interstitial space between the liner; placing a fuel storage rack in the pool; inserting at least one nuclear fuel assembly into the storage rack, the fuel assembly including a plurality of spent nuclear fuel rods; heating the cooling water in the pool to a first temperature from decay heat generated by the spent nuclear fuel rods; drawing a vacuum in the interstitial space with a vacuum pump to a negative pressure having a corresponding boiling point temperature less than the first temperature; collecting cooling water leaking from the pool through the liner system in the interstitial space; converting the leaking cooling water into vapor via boiling; and extracting the vapor from the interstitial space using the vacuum pump; wherein the presence of vapor in the interstitial space allows detection of a liner breach. The method may further include discharging the vapor extracted by the vacuum pump through a charcoal filter to remove contaminants. The method may further include: monitoring a pressure in the interstitial space; detecting a first pressure in the interstitial space prior to collecting cooling water leaking from the pool through the liner system in the interstitial space; and detecting a second pressure higher than the first pressure after collecting cooling water leaking from the pool through the liner system in the interstitial space; wherein the second pressure is associated with a cooling water leakage condition.
  • BRIEF DESCRIPTION OF THE DRAWINGS
  • The features of the exemplary embodiments will be described with reference to the following drawings where like elements are labeled similarly, and in which:
  • FIG. 1 is a cross sectional diagram of a known approach used to monitor the integrity of weld seams for leakage in a single spent fuel pool liner system;
  • FIG. 2 is a side cross-sectional view of an environmentally sequestered nuclear spent fuel pool having a dual liner and leakage collection and monitoring system according to the present disclosure;
  • FIG. 3 is a top plan view of the fuel pool with liner and leakage collection/monitoring system of FIG. 2;
  • FIG. 4 is a detail taken from FIG. 2 showing a bottom joint of the liner system at the intersection of liners from the sidewalls and base slab of the fuel pool;
  • FIG. 5 is a detail taken from FIG. 2 showing a top joint of the liner system at the terminal top ends of the sidewall liners;
  • FIG. 6 is a perspective view of an example nuclear fuel assembly containing spent nuclear fuel rods; and
  • FIG. 7 is a schematic diagram of a vacuum leakage collection and monitoring system according to the present disclosure.
  • All drawings are schematic and not necessarily to scale. Parts shown and/or given a reference numerical designation in one figure may be considered to be the same parts where they appear in other figures without a numerical designation for brevity unless specifically labeled with a different part number and described herein. References herein to a figure number (e.g. FIG. 1) shall be construed to be a reference to all subpart figures in the group (e.g. FIGS. 1A, 1B, etc.) unless otherwise indicated.
  • DETAILED DESCRIPTION
  • The features and benefits of the invention are illustrated and described herein by reference to exemplary embodiments. This description of exemplary embodiments is intended to be read in connection with the accompanying drawings, which are to be considered part of the entire written description. Accordingly, the disclosure expressly should not be limited to such exemplary embodiments illustrating some possible non-limiting combination of features that may exist alone or in other combinations of features.
  • In the description of embodiments disclosed herein, any reference to direction or orientation is merely intended for convenience of description and is not intended in any way to limit the scope of the present invention. Relative terms such as “lower,” “upper,” “horizontal,” “vertical,”, “above,” “below,” “up,” “down,” “top” and “bottom” as well as derivative thereof (e.g., “horizontally,” “downwardly,” “upwardly,” etc.) should be construed to refer to the orientation as then described or as shown in the drawing under discussion. These relative terms are for convenience of description only and do not require that the apparatus be constructed or operated in a particular orientation. Terms such as “attached,” “affixed,” “connected,” “coupled,” “interconnected,” and similar refer to a relationship wherein structures are secured or attached to one another either directly or indirectly through intervening structures, as well as both movable or rigid attachments or relationships, unless expressly described otherwise.
  • Referring to FIGS. 2-6, an environmentally sequestered spent fuel pool system includes a spent fuel pool 40 comprising a plurality of vertical sidewalls 41 rising upwards from an adjoining substantially horizontal base wall or slab 42 (recognizing that some slope may intentionally be provided in the upper surface of the bottom wall for drainage toward a low point if the pool is to be emptied and rinsed/decontaminated at some time and due to installation tolerances). The base slab 42 and sidewalls 41 may be formed of reinforced concrete in one non-limiting embodiment. The fuel pool base slab 42 may be formed in and rest on the soil sub-grade 26 the top surface of which defines grade G. In this embodiment illustrated in the present application, the sidewalls are elevated above grade. In other possible embodiments contemplated, the base slab 42 and sidewalls 41 may alternatively be buried in sub-grade 26 which surrounds the outer surfaces of the sidewalls. Either arrangement may be used and does not limit of the invention.
  • In one embodiment, the spent fuel pool 40 may have a rectilinear shape in top plan view. Four sidewalls 41 may be provided in which the pool has an elongated rectangular shape (in top plan view) with two longer opposing sidewalls and two shorter opposing sidewalls (e.g. end walls). Other configurations of the fuel pool 40 are possible such as square shapes, other polygonal shapes, and non-polygonal shapes.
  • The sidewalls 41 and base slab 42 of the spent fuel pool 40 define a cavity 43 configured to hold cooling pool water W and a plurality of submerged nuclear spent fuel assembly storage racks 27 holding fuel bundles or assemblies 28 each containing multiple individual nuclear spent fuel rods. The storage racks 27 are disposed on the base slab 42 in typical fashion. With continuing reference to FIGS. 1-6, the spent fuel pool 40 extends from an operating deck 22 surrounding the spent fuel pool 40 downwards to a sufficient depth D1 to submerge the fuel assemblies 28 (see, e.g. FIG. 6) beneath the surface level S of the pool water W for proper radiation shielding purposes. In one implementation, the fuel pool may have a depth such that at least 10 feet of water is present above the top of the fuel assembly.
  • A nuclear fuel assembly storage rack 27 is shown in FIGS. 2 and 3, and further described in commonly assigned U.S. patent application Ser. No. 14/367,705 filed Jun. 20, 1014, which is incorporated herein by reference in its entirety. The storage rack 27 contains a plurality of vertically elongated individual cells as shown each configured for holding a fuel assembly 28 comprising a plurality of individual nuclear fuel rods. An elongated fuel assembly 28 is shown in FIG. 6 holding multiple fuel rods 28 a and further described in commonly assigned U.S. patent application Ser. No. 14/413,807 filed Jul. 9, 2013, which is incorporated herein by reference in its entirety. Typical fuel assemblies 28 for a pressurized water reactor (PWR) may each hold over 150 fuel rods in 10×10 to 17×17 fuel rod grid arrays per assembly. The assemblies may typically be on the order of approximately 14 feet high weighing about 1400-1500 pounds each.
  • The substantially horizontal operating deck 22 that circumscribes the sidewalls 41 and pool 40 on all sides in one embodiment may be formed of steel and/or reinforced concrete. The surface level of pool water W (i.e. liquid coolant) in the pool 40 may be spaced below the operating deck 22 by a sufficient amount to prevent spillage onto the deck during fuel assembly loading or unloading operations and to account to seismic event. In one non-limiting embodiment, for example, the surface of the operating deck 22 may be at least 5 feet above the maximum 100 year flood level for the site in one embodiment. The spent fuel pool 40 extending below the operating deck level may be approximately 40 feet or more deep (e.g. 42 feet in one embodiment). The fuel pool is long enough to accommodate as many spent fuel assemblies as required. In one embodiment, the fuel pool 40 may be about 60 feet wide. There is sufficient operating deck space around the pool to provide space for the work crew and for staging necessary tools and equipment for the facility's maintenance. There may be no penetrations in the spent fuel pool 40 within the bottom 30 feet of depth to prevent accidental draining of water and uncovering of the spent fuel.
  • According to one aspect of the invention, a spent fuel pool liner system comprising a double liner is provided to minimize the risk of pool water leakage to the environment. The liner system is further designed to accommodate cooling water leakage collection and detection/monitoring to indicate a leakage condition caused by a breach in the integrity of the liner system.
  • The liner system comprises a first outer liner 60 separated from a second inner liner 61 by an interstitial space 62 formed between the liners. An outside surface of liner 60 is disposed against or at least proximate to the inner surface 63 of the fuel pool sidewalls 41 and opposing inside surface is disposed proximate to the interstitial space 62 and outside surface of liner 61. The inside surface of liner 61 is contacted and wetted by the fuel pool water W. It bears noting that placement of liner 60 against liner 61 without spacers therebetween provides a natural interstitial space of sufficient width to allow the space and any pool leakage there-into to be evacuated by a vacuum system, as further described herein. The natural surface roughness of the materials used to construct the liners and slight variations in flatness provides the needed space or gap between the liners. In other embodiments contemplated, however, metallic or non-metallic spacers may be provided which are distributed in the interstitial space 62 between the liners if desired.
  • The liners 60, 61 may be made of any suitable metal which is preferably resistant to corrosion, including without limitation stainless steel, aluminum, or other. In some embodiments, each liner may be comprised of multiple substantially flat metal plates which are seal welded together along their peripheral edges to form a continuous liner system encapsulating the sidewalls 41 and base slab 42 of the spent fuel pool 40.
  • The inner and outer liners 61, 60 may have the same or different thicknesses (measured horizontally or vertically between major opposing surfaces of the liners depending on the position of the liners). In one embodiment, the thicknesses may be the same. In some instances, however, it may be preferable that the inner liner 61 be thicker than the outer liner 60 for potential impact resistant when initially loading empty fuel storage racks 27 into the spent fuel pool 40.
  • The outer and inner liners 60, 61 (with interstitial space therebetween) extend along the vertical sidewalls 41 of the spent fuel pool 40 and completely across the horizontal base slab 42 in one embodiment to completely cover the wetted surface area of the pool. This forms horizontal sections 60 b, 61 b and vertical sections 60 a, 61 a of the liners 60, 61 to provide an impervious barrier to out-leakage of pool water W from spent fuel pool 40. The horizontal sections of liners 60 b, 61 b on the base slab 42 may be joined to the vertical sections 60 a, 61 a along the sidewalls 41 of the pool 40 by welding. The detail in FIG. 4 shows one or many possible constructions of the bottom liner joint 64 comprising the use of seal welds 65 (e.g. illustrated fillet welds or other) to seal sections 60 a to 60 b along their respective terminal edges and sections 61 a to 61 b along their respective terminal edges as shown. Preferably, the joint 64 is configured and arranged to fluidly connect the horizontal interstitial space 64 between horizontal liner sections 60 b, 61 b to the vertical interstitial space 64 between vertical liner sections 60 a, 61 a for reasons explained elsewhere herein.
  • The top liner joint 65 in one non-limiting embodiment between the top terminal edges 60 c, 61 c of the vertical liner sections 60 a, 61 a is shown in the detail of FIG. 5. The top of the spent fuel pool 40 is equipped with a substantially thick metal embedment plate 70 which circumscribes the entire perimeter of the fuel pool. The embedment plate 70 may be continuous in one embodiment and extends horizontally along the entire inner surface 63 of the sidewalls 41 at the top portion of the sidewalls. The embedment plate 70 has an exposed portion of the inner vertical side facing the pool which extends above the top terminal ends 60 c, 61 c of the inner and outer liners 60, 61. The opposing outer vertical side of the plate 70 is embedded entirely into the sidewalls 41. A top surface 71 of the embedment plate 70 that faces upwards may be substantially flush with the top surface 44 of the sidewalls 41 to form a smooth transition therebetween. In other possible implementations, the top surface 71 may extend above the top surface 44 of the sidewalls. The embedment plate 70 extends horizontal outward from the fuel pool 40 for a distance into and less than the lateral width of the sidewalls 41 as shown.
  • The embedment plate 70 has a horizontal thickness greater than the horizontal thickness of the inner liner 61, outer liner 60, and in some embodiments both the inner and outer liners combined.
  • The top embedment plate 70 is embedded into the top surface 44 of the concrete sidewalls 41 has a sufficient vertical depth or height to allow the top terminal edges 60 c, 61 c of liners 60, 61 (i.e. sections 60 a and 61 a respectively) to be permanently joined to the plate. The top terminal edges of liners 60, 61 terminate at distances D2 and D1 respectively below a top surface 71 of the embedment plate 70 (which in one embodiment may be flush with the top surface of the pool sidewalls 41 as shown). Distance D1 is less than D2 such that the outer liner 60 is vertical shorter in height than the inner liner 61. In one embodiment, the embedment plate 70 has a bottom end which terminates below the top terminal edges 60 c, 61 c of the liners 60, 61 to facilitate for welding the liners to the plate.
  • In various embodiments, the embedment plate 70 may be formed of a suitable corrosion resistant metal such as stainless steel, aluminum, or another metal which preferably is compatible for welding to the metal used to construct the outer and inner pool liners 60, 61 without requiring dissimilar metal welding.
  • As best shown in FIG. 5, the top terminal edges 60 c, 61 c of inner and outer liners 60, 61 may have a vertically staggered arranged and be separately seal welded to the top embedment plate 70 independently of each other. A seal weld 66 couples the top terminal edge 61 c of liner 61 to the exposed portion of the inner vertical side of the embedment plate 70. A second seal weld 67 couples the top terminal edge 60 c of liner 60 also to the exposed portion of the inner vertical side of the embedment plate 70 at a location below and spaced vertical apart from seal weld 66. This defines a completely and hermetically sealed enclosed flow plenum 68 that horizontal circumscribes the entire perimeter of the spent fuel pool 40 in one embodiment. The flow plenum 68 is in fluid communication with the interstitial space 62 as shown. One vertical side of the flow plenum is bounded by a portion of inner liner 61 and the opposing vertical side of the plenum is bounded by the inner vertical side of the top embedment plate 70.
  • The top flow plenum 68 may be continuous or discontinuous in some embodiments. Where discontinuous, it is preferable that a flow passageway 105 in the top embedment plate 70 be provided for each section of the separate passageways.
  • Seal welds 66 and 67 may be any type of suitable weld needed to seal the liners 60, 61 to the top embedment plate 70. Backer plates, bars, or other similar welding accessories may be used to make the welds as needed depending on the configuration and dimensions of the welds used. The invention is not limited by the type of weld.
  • In one embodiment, the outer and inner liners 60, 61 are sealably attached to the spent fuel pool 40 only at top embedment plate 70. The remaining portions of the liners below the embedment plate may be in abutting contact with the sidewalls 41 and base slab 42 without means for fixing the liners to these portions.
  • It bears noting that at least the inner liner 61 has a height which preferably is higher than the anticipated highest water level (surface S) of the pool water W in one embodiment. If the water level happens to exceed that for some reason, the top embedment plate 70 will be wetted directly by the pool water and contain the fluid to prevent overflowing the pool onto the operating deck 22.
  • According to another aspect of the invention, a vapor extraction or vacuum system 100 is provided that is used to draw down the air pressure in the interstitial space between the outer and inner liners 60, 61 to a relatively high state of vacuum for leakage control and/or detection. FIG. 7 is a schematic diagram of one embodiment of a vacuum system 100.
  • Referring to FIGS. 5 and 7, vacuum system 100 generally includes a vacuum pump 101 and a charcoal filter 102. Vacuum pump 101 may be any suitable commercially-available electric-driven vacuum pump capable of creating a vacuum or negative pressure within the interstitial space 62 between the pool liners 60 and 61. The vacuum pump 101 is fluidly connected to the interstitial space 68 via a suitable flow conduit 103 which is fluidly coupled to a telltale or flow passageway 105 extending from the top surface 71 of the top embedment plate 70 to the top flow plenum 68 formed between the pool liners 60 and 61. Flow conduit 103 may be formed of any suitable metallic or non-metallic tubing or piping capable of withstanding a vacuum. A suitably-configured fluid coupling 104 may be provided and sealed to the outlet end of the flow passageway 105 for connecting the flow conduit 103. The inlet end of the flow passageway penetrates the inner vertical side of top embedment plate 70 within the flow plenum 68. The flow passageway 105 and external flow conduit 103 provides a contiguous flow conduit that fluidly couples the flow plenum 68 to the vacuum pump 101. A one-way check valve is disposed between the flow plenum 105 and the suction inlet of the vacuum pump 101 to permit air and/or vapor to flow in a single direction from the liner system to the pump.
  • The absolute pressure maintained by the vacuum system 100 in the interstitial space 62 between the liners 60, 61 (i.e. “set pressure”) preferably should be such that the bulk water temperature of the spent fuel pool 40 which is heated by waste decay heat generated from the fuel rods/assemblies is above the boiling temperature of water at the set pressure. The table below provides the boiling temperature of water at the level of vacuum in inches of mercury (Hg) which represent some examples of set pressures that may be used.
  • Pressure in inch, HgA Boiling Temp, deg F.
    1 79
    2 101
    3 115
    4 125
    5 133
  • Any significant rise in pressure would indicate potential leakage of water in the interstitial space 62 between the liners 60, 61. Because of sub-atmospheric conditions maintained by the vacuum pump 101 in the interstitial space, any water that may leak from the pool into this space through the inner liner 61 would evaporate, causing the pressure to rise which may be monitored and detected by a pressure sensor 104. The vacuum pump 101 preferably should be set to run and drive down the pressure in the interstitial space 62 to the “set pressure.”
  • In operation as one non-limiting example, if the vacuum pump 101 is operated to create a negative pressure (vacuum) in the interstitial space 62 of 2 inches of Hg, the corresponding boiling point of water at that negative pressure is 101 degrees Fahrenheit (degrees F.) from the above Table. If the bulk water temperature of pool water W in the spent fuel pool 40 were at any temperature above 101 degrees F. and leakage occurred through the inner pool liner 61 into the interstitial space 62, the liquid leakage would immediately evaporate therein creating steam or vapor. The vacuum pump 101 withdraws the vapor through the flow plenum 68, flow passageway 105 in the top embedment plate 70, and flow conduit 103 (see, e.g. directional flow arrows of the water vapor in FIGS. 5 and 7). Pressure sensor 104 disposed on the suction side of the pump 101 would detect a corresponding rise in pressure indicative of a potential leak in the liner system. In some embodiments, the pressure sensor 104 may be operably linked to a control panel of a properly configured computer processor based plant monitoring system 107 which monitors and detects the pressure measured in the interstitial space 62 between the liners on a continuous or intermittent basis to alert operators of a potential pool leakage condition. Such plant monitoring systems are well known in the art without further elaboration.
  • The extracted vapor in the exhaust or discharge from the vacuum pump 101 is routed through a suitable filtration device 102 such as a charcoal filter or other type of filter media before discharge to the atmosphere, thereby preventing release of any particulate contaminants to the environment.
  • Advantageously, it bears noting that if leakage is detected from the spent fuel pool 40 via the vacuum system 100, the second outer liner 60 encapsulating the fuel pool provides a secondary barrier and line of defense to prevent direct leaking of pool water W into the environment.
  • It bears noting that there is no limit to the number of vapor extraction systems including a telltale passageway, vacuum pump, and filter combination with leakage monitoring/detection capabilities that may be provided. In some instances, four independent systems may provide adequate redundancy. In addition, it is also recognized that a third or even fourth layer of liner may be added to increase the number of barriers against leakage of pool water to the environment. A third layer in some instances may be used as a palliative measure if the leak tightness of the first inter-liner space could not, for whatever reason, be demonstrated by a high fidelity examination in the field such as helium spectroscopy.
  • While the foregoing description and drawings represent exemplary embodiments of the present disclosure, it will be understood that various additions, modifications and substitutions may be made therein without departing from the spirit and scope and range of equivalents of the accompanying claims. In particular, it will be clear to those skilled in the art that the present invention may be embodied in other forms, structures, arrangements, proportions, sizes, and with other elements, materials, and components, without departing from the spirit or essential characteristics thereof. In addition, numerous variations in the methods/processes described herein may be made within the scope of the present disclosure. One skilled in the art will further appreciate that the embodiments may be used with many modifications of structure, arrangement, proportions, sizes, materials, and components and otherwise, used in the practice of the disclosure, which are particularly adapted to specific environments and operative requirements without departing from the principles described herein. The presently disclosed embodiments are therefore to be considered in all respects as illustrative and not restrictive. The appended claims should be construed broadly, to include other variants and embodiments of the disclosure, which may be made by those skilled in the art without departing from the scope and range of equivalents.

Claims (20)

What is claimed is:
1. A spent fuel pool system comprising:
a fuel pool comprising:
a base slab;
a plurality of vertical sidewalls extending from the base slab; and
a cavity defined by the vertical sidewalls and the base slab, the cavity being at least partially filled with pool water;
a pool liner system located within the cavity, the pool liner system comprising:
an outer liner positioned adjacent to the vertical sidewalls;
an inner liner positioned adjacent to the outer liner such that the inner liner is in contact with the pool water; and
wherein the inner and outer liners are separated by an air gap.
2. The spent fuel pool system according to claim 1 wherein both of the inner and outer liners are positioned within the cavity of the fuel pool.
3. The spent fuel pool system according to claim 1 further comprising an embedment plate embedded into the vertical sidewalls and circumscribing the cavity, the embedment plate comprising an inner surface that faces the cavity.
4. The spent fuel pool system according to claim 3 wherein the inner liner is sealably coupled to the inner surface of the embedment plate at a first position and the outer liner is sealably coupled to the inner surface of the embedment plate at a second position, the first position being closer to an open top end of the cavity than the second position.
5. The spent fuel pool system according to claim 4 wherein a hermetically sealed flow plenum is formed between a top terminal edge of the inner liner and a top terminal edge of the outer liner, wherein the flow plenum is in fluid communication with the air gap.
6. The spent fuel pool system according to claim 5 further comprising a flow passageway formed through the embedment plate, a first end of the flow passageway being fluidly coupled to the flow plenum.
7. The spent fuel pool system according to claim 6 further comprising a vacuum system located outside of the cavity of the fuel pool, the vacuum system comprising a vacuum pump that is fluidly coupled to the air gap by way of the flow passageway of the embedment plate.
8. The spent fuel pool system according to claim 7 wherein the vacuum pump is configured to maintain the air gap at a vacuum pressure.
9. The spent fuel pool system according to claim 8 further comprising a pressure sensor configured to detect any rise in pressure within the air gap that would be indicative of a potential leak in the pool liner system.
10. The spent fuel pool system according to claim 5 wherein the flow plenum extends around an entire perimeter of the spent fuel pool.
11. The spent fuel pool system according to claim 1 wherein the air gap extends interrupted from an inner surface of the outer liner that faces away from the vertical sidewalls and towards the cavity to an outer surface of the inner liner that faces away from the cavity and towards the vertical sidewalls.
12. The spent fuel pool system according to claim 1 further comprising a plurality of storage racks disposed on the base slab and submerged in the pool water, each of the storage racks having a plurality of cells each configured for holding a spent nuclear fuel assembly containing nuclear fuel rods.
13. The spent fuel pool system according to claim 1 wherein the inner and outer liners are located entirely within the cavity of the fuel pool.
14. A spent fuel pool system comprising:
a fuel pool comprising:
a base slab;
a plurality of vertical sidewalls extending from the base slab; and
a cavity defined by the base slab and an inner surface of the vertical sidewalls, the cavity being filled with pool water;
a pool liner system comprising:
an outer liner positioned adjacent to the inner surfaces of the vertical sidewalls; and
an inner liner positioned adjacent to the outer liner, the inner liner being spaced apart from the outer liner by an air gap, and wherein the inner liner is in contact with the pool water; and
a vacuum system fluidly coupled to the air gap, the vacuum system comprising a vacuum pump that is configured to maintain the air gap at a vacuum pressure.
15. The spent fuel pool system according to claim 14 further comprising a pressure sensor configured to detect any rise in pressure within the air gap that would be indicative of a potential leak in the pool liner system.
16. The spent fuel pool system according to claim 14 further comprising a flow plenum formed between a top terminal edge of the outer liner and a top terminal edge of the inner liner, the flow plenum being fluidly coupled to the air gap between the inner and outer liners.
17. The spent fuel pool system according to claim 16 wherein the vacuum pump is fluidly coupled to the air plenum through a flow passageway formed into an embedment plate that is embedded within the vertical sidewalls.
18. A spent fuel pool system comprising:
a base slab;
a plurality of vertical sidewalls extending from the base slab;
a cavity defined by the vertical sidewalls and the base slab, the cavity being filled with pool water;
at least one fuel storage rack disposed in the cavity, the fuel storage rack holding a nuclear spent fuel assembly containing nuclear fuel rods that heat the pool water;
a pool liner system located in the cavity and comprising an outer liner adjacent the sidewalls and base slab, an inner liner adjacent the outer liner and wetted by the pool water, and an interstitial space formed between the outer and inner liners; and
a vacuum pump fluidly coupled to the interstitial space, the vacuum pump being configured to evacuate air from the interstitial space to maintain a pressure of the interstitial space below atmospheric pressure.
19. The spent fuel pool system according to claim 18 further comprising a pressure sensor configured to detect any rise in pressure within the air gap that would be indicative of a potential leak in the pool liner system.
20. The spent fuel pool system according to claim 19, further comprising a computer processor based plant monitoring system operably coupled to the pressure sensor to monitor the pressure of the interstitial space.
US16/584,892 2011-08-19 2019-09-26 Environmentally sequestered spent fuel pool Abandoned US20200035370A1 (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
US16/584,892 US20200035370A1 (en) 2014-10-07 2019-09-26 Environmentally sequestered spent fuel pool
US17/088,960 US11515054B2 (en) 2011-08-19 2020-11-04 Method of retrofitting a spent nuclear fuel storage system
US17/981,978 US20230082771A1 (en) 2011-08-19 2022-11-07 Method of retrofitting a spent nuclear fuel storage system

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
US201462061089P 2014-10-07 2014-10-07
US14/877,217 US10468145B2 (en) 2014-10-07 2015-10-07 Environmentally sequestered spent fuel pool
US16/584,892 US20200035370A1 (en) 2014-10-07 2019-09-26 Environmentally sequestered spent fuel pool

Related Parent Applications (2)

Application Number Title Priority Date Filing Date
US14/877,217 Continuation US10468145B2 (en) 2011-08-19 2015-10-07 Environmentally sequestered spent fuel pool
US16/513,815 Continuation-In-Part US10910119B2 (en) 2011-08-19 2019-07-17 Self-alignment method of neutron absorbing apparatus for reactivity mitigation in nuclear fuel storage systems

Related Child Applications (3)

Application Number Title Priority Date Filing Date
US14/811,454 Continuation-In-Part US10037826B2 (en) 2011-08-19 2015-07-28 Apparatus for supporting spent nuclear fuel
US16/729,654 Continuation-In-Part US20200243209A1 (en) 2011-08-19 2019-12-30 Snap-in insert for reactivity control in spent nuclear fuel pools and casks
US17/088,960 Continuation-In-Part US11515054B2 (en) 2011-08-19 2020-11-04 Method of retrofitting a spent nuclear fuel storage system

Publications (1)

Publication Number Publication Date
US20200035370A1 true US20200035370A1 (en) 2020-01-30

Family

ID=55633261

Family Applications (2)

Application Number Title Priority Date Filing Date
US14/877,217 Active 2035-12-11 US10468145B2 (en) 2011-08-19 2015-10-07 Environmentally sequestered spent fuel pool
US16/584,892 Abandoned US20200035370A1 (en) 2011-08-19 2019-09-26 Environmentally sequestered spent fuel pool

Family Applications Before (1)

Application Number Title Priority Date Filing Date
US14/877,217 Active 2035-12-11 US10468145B2 (en) 2011-08-19 2015-10-07 Environmentally sequestered spent fuel pool

Country Status (6)

Country Link
US (2) US10468145B2 (en)
EP (1) EP3204949B1 (en)
KR (1) KR101956628B1 (en)
CN (1) CN107077899B (en)
ES (1) ES2762940T3 (en)
WO (1) WO2016057636A1 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2021155776A1 (en) * 2020-02-04 2021-08-12 中国海洋石油集团有限公司 Radioactive source library
US11515054B2 (en) 2011-08-19 2022-11-29 Holtec International Method of retrofitting a spent nuclear fuel storage system

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB201510442D0 (en) * 2015-06-15 2015-07-29 Sensor Uk Ltd And Mwh Uk Ltd And Carlow Precast Mfg Fluid retaining structure
US10366797B2 (en) * 2015-09-17 2019-07-30 Korea Atomic Energy Research Institute System and method for preventing and monitoring leakage of water from tank liner
WO2018063022A1 (en) * 2016-09-30 2018-04-05 Акционерное Общество "Научно-Исследовательский И Проектно-Конструкторский Институт Энергетических Технологий "Атомпроект" System for monitoring leaks of liquid from a spent fuel pool
CN106297923A (en) * 2016-10-11 2017-01-04 上海核工程研究设计院 A kind of Spent Fuel Pool of pair of pond design
US10847274B2 (en) * 2017-02-24 2020-11-24 Holtec International Earthquake-resistant fuel storage rack system for fuel pools in nuclear plants
CN107511559B (en) * 2017-09-06 2020-10-20 中国核工业华兴建设有限公司 Installation method and welding process for double-phase stainless steel pool cover of nuclear power station
CN108172313A (en) * 2017-12-25 2018-06-15 中国建筑第二工程局有限公司 Used in nuclear power station stainless steel pond and welding method
JP7064991B2 (en) * 2018-07-30 2022-05-11 三菱重工業株式会社 Fuel pool and fuel pool lining construction method
KR102196292B1 (en) * 2018-09-05 2020-12-29 한국수력원자력 주식회사 Apparatus for cooling spent nuclear fuel and method for cooling spent nuclear fuel using the same
CN110246600A (en) * 2019-07-11 2019-09-17 上海核工程研究设计院有限公司 A kind of full underground type compact reactor refuling device
CN111564229B (en) * 2020-04-01 2023-11-24 中广核工程有限公司 Leakage detection method for nuclear power station pool steel cladding
CN112967823B (en) * 2021-01-29 2023-05-23 中国原子能科学研究院 Cover body assembly and pool reactor
TWI766720B (en) * 2021-06-09 2022-06-01 洽興營造有限公司 The final disposal site for underground low-level nuclear waste barrels

Family Cites Families (22)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3444725A (en) * 1967-04-06 1969-05-20 Stone & Webster Eng Corp Leak detecting and locating system for nuclear reactor containment vessels
US3430180A (en) * 1967-05-18 1969-02-25 Frank F Brown Electrical swivel connector
FR2209983B1 (en) 1972-12-13 1976-04-23 Technigaz
JPS5757233A (en) * 1980-09-24 1982-04-06 Hitachi Ltd Apparatus for detecting leakage in pool lining and manufacture thereof
DE3430180A1 (en) * 1984-08-16 1986-02-27 Kraftwerk Union AG, 4330 Mülheim Liner for a compartment in a nuclear installation
SU1408829A1 (en) 1985-05-11 1990-09-15 Ленинградское Отделение Всесоюзного Государственного Научно-Исследовательского И Проектно-Изыскательского Института "Атомтеплоэлектропроект" Method of constructing basin for storage of spent nuclear fuel
JPS63250600A (en) * 1987-04-08 1988-10-18 株式会社東芝 Radioactive solid-waste processor
US5102615A (en) * 1990-02-22 1992-04-07 Lou Grande Metal-clad container for radioactive material storage
US5184504A (en) 1990-05-30 1993-02-09 Spring G Everett Leak detection
FR2762132B1 (en) 1997-04-10 1999-06-18 Commissariat Energie Atomique TRANSPORTATION PACKAGE FOR DANGEROUS PACKAGES, SUCH AS HIGH-ACTIVITY NUCLEAR PACKAGES
US20040234338A1 (en) * 2003-05-19 2004-11-25 Monroe Thomas K. Secondary containment monitoring system
US7392690B2 (en) * 2004-09-03 2008-07-01 David D Russell Systems and methods for monitoring the integrity of a tank
US9443625B2 (en) 2005-03-25 2016-09-13 Holtec International, Inc. Method of storing high level radioactive waste
US7330526B2 (en) 2005-03-25 2008-02-12 Holtec International, Inc. System and method of storing high level waste
US8785805B2 (en) 2007-05-04 2014-07-22 Societat D'obres I Treballs Subterranis Del Pirineu, S.L. (Sots, S.L.) Method of making a covering for a containment pool, tank or enclosure
JP4593601B2 (en) * 2007-08-03 2010-12-08 キヤノンアネルバ株式会社 Pollutant removal method, semiconductor manufacturing method, and thin film forming apparatus
US8718221B2 (en) 2009-12-16 2014-05-06 Holtec International, Inc. Method of transferring high level radioactive materials, and system for the same
US8905259B2 (en) 2010-08-12 2014-12-09 Holtec International, Inc. Ventilated system for storing high level radioactive waste
WO2014036561A2 (en) 2012-08-31 2014-03-06 Holtec International, Inc. System and method for storing and leak testing a radioactive materials storage canister
US9466400B2 (en) 2013-01-25 2016-10-11 Holtec International Ventilated transfer cask with lifting feature
US9646726B2 (en) 2013-02-06 2017-05-09 Westinghouse Electric Company Llc Alternate passive spent fuel pool cooling systems and methods
US20160045841A1 (en) 2013-03-15 2016-02-18 Transtar Group, Ltd. New and improved system for processing various chemicals and materials

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11515054B2 (en) 2011-08-19 2022-11-29 Holtec International Method of retrofitting a spent nuclear fuel storage system
WO2021155776A1 (en) * 2020-02-04 2021-08-12 中国海洋石油集团有限公司 Radioactive source library

Also Published As

Publication number Publication date
US20160099085A1 (en) 2016-04-07
CN107077899A (en) 2017-08-18
EP3204949A1 (en) 2017-08-16
WO2016057636A1 (en) 2016-04-14
KR20170067831A (en) 2017-06-16
KR101956628B1 (en) 2019-03-11
ES2762940T3 (en) 2020-05-26
US10468145B2 (en) 2019-11-05
EP3204949A4 (en) 2018-06-20
CN107077899B (en) 2019-11-12
EP3204949B1 (en) 2019-09-04

Similar Documents

Publication Publication Date Title
US20200035370A1 (en) Environmentally sequestered spent fuel pool
EP3195325B1 (en) An ultra-safe wet storage facility for nuclear fuel
CN108511098B (en) High anti-seismic fuel storage rack system for fuel pool of nuclear power plant
US9916910B2 (en) Passively-cooled spent nuclear fuel pool system and method therefor
US5971009A (en) Dual containment assembly
JPH02285300A (en) Checkable bolt apparatus for poisonous waste disposal
US20140226777A1 (en) Ventilated system for storing high level radioactive waste
EP3134900B1 (en) Storage system for nuclear fuel
US5460032A (en) Impoundment leak detection, location, and containment system
JPH02287198A (en) Bolt apparatus for radioactive waste disposal and waste disposal method
KR20220050975A (en) Radiation shielding enclosures for spent fuel casks
CA2598478C (en) Plant for storing gas under pressure
KR101574378B1 (en) Radiation shield to be installed in a varying clearance gap
US4473974A (en) Storage tank and method for manufacturing the same
WO2016031322A1 (en) Building
CN105280255A (en) Underground storage silo for storing nuclear power plant fuel storage tank
TW201611036A (en) Nuclear power plant and reactor building gas treatment system
JPH03115998A (en) Method and structure for shielding radiation from incore structure in storage condition
JP6056284B2 (en) Reactor removal method
JP2014223559A (en) Vertical wall structure of waste storage facility
US5179971A (en) Sidewall support for dual containment vessels
US11515054B2 (en) Method of retrofitting a spent nuclear fuel storage system
JP2014178142A (en) Reactor containment vessel cooling system and cooling method
CN108447575B (en) Dry type storage loading method for spent fuel of pressurized water reactor
KR101761765B1 (en) Pool equipped with leak prevention system and leak monitoring method for pool

Legal Events

Date Code Title Description
AS Assignment

Owner name: HOLTEC INTERNATIONAL, NEW JERSEY

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNOR:SINGH, KRISHNA P;REEL/FRAME:050509/0199

Effective date: 20150409

STPP Information on status: patent application and granting procedure in general

Free format text: DOCKETED NEW CASE - READY FOR EXAMINATION

STPP Information on status: patent application and granting procedure in general

Free format text: NON FINAL ACTION MAILED

STCB Information on status: application discontinuation

Free format text: ABANDONED -- FAILURE TO RESPOND TO AN OFFICE ACTION